Abstract
A simple method for the evaluation of the burnup of a materials testing reactor (MTR) fuel element by gamma spectrometry is presented. The method was applied to a highly enriched uranium MTR nuclear fuel element that was irradiated in a 5 MW pool-type research reactor for a total period of 34 years. The experimental approach is based on in-situ measurements of the MTR fuel element in the reactor pool by a portable high-purity germanium detector located in a gamma cell. To corroborate the method, analytical calculations (based on the irradiation history of the fuel element) and computer simulations using a dedicated fuel cycle burnup code ORIGEN2 were performed. The burnup of the MTR fuel element was found to be 52.4±8.8%, which is in good agreement with the analytical calculations and the computer simulations. The method presented here is suitable for research reactors with either a regular or an irregular irradiation regime and for reactors with limited infrastructure and/or resources. In addition, its simplicity and the enhanced safety it confers may render this method suitable for IAEA inspectors in fuel element burnup assessments during on-site inspections.
| Original language | English |
|---|---|
| Pages (from-to) | 175-182 |
| Number of pages | 8 |
| Journal | Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment |
| Volume | 834 |
| DOIs | |
| State | Published - 21 Oct 2016 |
Keywords
- Depletion calculations
- Fission products
- Fuel burnup
- Gamma spectrometry
- MTR reactor
ASJC Scopus subject areas
- Nuclear and High Energy Physics
- Instrumentation
Fingerprint
Dive into the research topics of 'A simple gamma spectrometry method for evaluating the burnup of MTR-type HEU fuel elements'. Together they form a unique fingerprint.Cite this
- APA
- Author
- BIBTEX
- Harvard
- Standard
- RIS
- Vancouver